Reduced-activation bainitic and martensitic steels for nuclear fusion applications

Current Opinion in Solid State and Materials Science

Volumn 8, Issue 3-4, 2004, Pages 239-250

  Klueh, R L ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

Bainite; Martensite; Mechanical properties; Steel

Indexed keywords

ACTIVATION ANALYSIS; BAINITE; ENVIRONMENTAL IMPACT; FUSION REACTIONS; MARTENSITE; NEUTRON IRRADIATION; POWER GENERATION; POWER PLANTS; RADIOACTIVE ELEMENTS; THERMAL EFFECTS;

BLANKET STRUCTURES; LOW-ACTIVATION STRUCTURAL MATERIALS; REDUCED-ACTIVATION STEELS; TRANSMUTATION;

STEEL;

EID: 13444301419     PISSN: 13590286     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.cossms.2004.09.004     Document Type: Article

References (68)

1. R.L. Klueh, and D.R. Harries High-chromium ferritic and martensitic steels for nuclear applications 2002 American Society for Testing and Materials West Conshohocken, PA
2. R.W. Conn, E.E. Bloom, J.W. Davis, R.E. Gold, R. Little, and K.R. Schultz Report on low activation materials for fusion applications Nucl Tech/Fusion 5 1984 291 310
3. G.W. Butterworth, and O.N. Jarvis Comparison of transmutation and activation effects in five ferritic alloys and AISI 316 stainless steel J Nucl Mater 122&123 1984 982 988
4. N.M. Ghoniem, A. Shabaik, and M.Z. Youssef Development of low activation vanadium steel for fusion applications J.W. Davis D.J. Michel Proceedings of topical conference for ferritic steels for use in nuclear energy technologies 1984 The Metallurgical Society of AIME Warrendale, PA 201 208
5. R.L. Klueh, and E.E. Bloom The development of ferritic steels for fast induced-radioactivity decay for fusion reactor applications Nucl Eng Des/Fusion 2 1985 383 389
6. D.S. Gelles Optimization of martensitic stainless steels for nuclear reactor applications F.A. Garner D.S. Gelles F.W. Wiffen Optimizing materials for nuclear applications 1985 The Metallurgical Society of AIME Warrendale, PA 63 71
7. D. Dulieu, K.W. Tupholme, and G.J. Butterworth Development of low-activation martensitic stainless steels J Nucl Mater 141-143 1986 1097 1101
8. M. Tamura, H. Hayakawa, M. Tanimura, A. Hishinuma, and T. Kondo Development of potential low activation ferritic and austenitic steels J Nucl Mater 141-143 1986 1067 1073
9. T. Noda, F. Abe, H. Araki, and M. Okada Development of low activation ferritic steels J Nucl Mater 141-143 1986 1102 1106
10. R.L. Klueh, D.S. Gelles, and T.A. Lechtenberg Development of ferritic steels for reduced activation: the US program J Nucl Mater 141-143 1986 1081 1087
11. D.S. Gelles Effects of irradiation on low activation ferritic alloys: a review R.L. Klueh D.S. Gelles M. Okada N.H. Packan Reduced activation materials for fusion reactors, ASTM STP 1047 1990 American Society for Testing and Materials Philadelphia 113 129
12. C.Y. Hsu, and T.A. Lechtenberg Microstructure and mechanical properties of unirradiated low activation ferritic steel J Nucl Mater 141-143 1986 1107 1112
13. Anderko K, Ehrlich K, Schäfer L, Schirra M. CETA-EinEntwicklungsschritt zu einem Schwach Activierbaren martensitischen Chromstahl, Kernforschungszentrum Karlsruhe. KfK Report 5060, June 1993
14. H. Kayano, H. Kurishita, A. Kimura, M. Narui, M. Yamazaki, and Y. Suzuki Charpy impact testing using miniature specimens and its application to the study of irradiation behavior of low-activation ferritic steels J Nucl Mater 179-181 1991 425 428
15. R.L. Klueh, and P.J. Maziasz Microstructure of Cr-W steels Met Trans A 20 1989 373 381
16. M. Tamura, H. Hayakawa, M. Tanimura, A. Hishinuma, and T. Kondo Phase stability of reduced activation ferritic steel: 8%Cr-2%V-0.04%Ta-Fe J Nucl Mater 155-157 1988 620 625
17. M. Yamanouchi, M. Tamura, H. Hayakawa, A. Hishinuma, and T. Kondo Accumulation of engineering data for practical use of reduced activation ferritic steel: 8%Cr-2%W-0.2%V-0.04%Ta-Fe J Nucl Mater 191-194 1992 822 826
18. F. Abe, T. Noda, H. Araki, and S. Nakazawa Alloy composition selection for improving strength and toughness of reduced activation 9Cr-W steels J Nucl Mater 179-181 1991 663 666
19. A. Kohyama, Y. Kohno, K. Asakura, and H. Kayano R&D of low activation ferritic steels for fusion in Japanese universities J Nucl Mater 212-215 1994 684 689
20. K. Ehrlich, S. Kelzenberg, H.D. Röhrig, L. Schäfer, and M. Schirra The development of ferritic-martensitic steels with reduced long-term activation J Nucl Mater 212-215 1994 678 683
21. R.L. Klueh Heat treatment behavior and tensile behavior of Cr-W steels Met Trans A 20 1989 463 469
22. M.S. Tillack, X.R. Wang, J. Pulsifer, S. Malang, and D.K. Sze ARIES-ST breeding blanket design and analysis Fusion Eng Des 49-50 2000 689 695
23. H.U. Borgstedt, H. Glasbrenner, and Z. Peric Corrosion of insulating layers on MANET steel in flowing Pb-Li J Nucl Mater 212-215 1994 1501 1503
24. V.S. Agueev, V.N. Bykov, A.M. Dvoryashin, V.N. Golovanov, E.A. Medvendeva, and V.V. Romaneev Influence of structure and phase composition on 1Cr13Mo2NbVB steel mechanical properties in initial, aged, and irradiated states N.E. Packan R.E. Stoller A.S. Kumar Effects of radiation on materials: 14th international symposium, ASTM STP 1046 vol. 1 1989 American Society for Testing and Materials Philadelphia 98 113
25. P.J. Maziasz, R.L. Klueh, and J.M. Vitek Helium effects on void formation in 9Cr-1MoVNb and 12Cr-1MoVW irradiated in HFIR J Nucl Mater 141-143 1986 929 937
26. J.J. Kai, and R.L. Klueh Microstructural analysis of neutron-irradiated martensitic steels J Nucl Mater 230 1996 116 123
27. D.S. Gelles Microstructural development in reduced activation ferritic alloys irradiated to 200 dpa at 420 °C J Nucl Mater 212-215 1994 714 719
28. E.A. Little, and L.P. Stoter H.R. Brager J.S. Perrin Effects of irradiation on materials: eleventh conference, ASTM STP 782 1982 American Society for Testing and Materials Philadelphia 207 233
29. D.S. Gelles, and L.E. Thomas Effects of neutron irradiation on microstructure in experimental and commercial ferritic alloys J.W. Davis D.J. Michel Proceedings of topical conference for ferritic steels for use in nuclear energy technologies 1984 The Metallurgical Society of AIME Warrendale, PA 559 567
30. J.D. Hunn, M.B. Lewis, and E.H. Lee Hydrogen retention in ion-irradiated steels Second international topical meeting on nuclear applications of accelerator technology 1998 American Nuclear Society La Grange Park, IL 375 381
31. P. Marmy, and B.M. Oliver High strain fatigue properties of F82H ferritic-martensitic steel under proton irradiation J Nucl Mater 318 2003 132 142
32. Y. Dai, Y. Foucher, M.R. James, and B.M. Oliver Neutronics calculation, dosimetry analysis and gas measurements of the first SINQ target irradiation experiment, STIP-I J Nucl Mater 318 2003 167 175
33. C. Wassilew, K. Herschbach, E. Materna-Morris, and K. Ehrlich Irradiation behaviour of 12% Cr martensitic steels J.W. Davis D.J. Michel Proceedings of topical conference for ferritic steels for use in nuclear energy technologies 1984 The Metallurgical Society of AIME Warrendale, PA 607 614
34. R.L. Klueh, and J.M. Vitek Elevated-temperature tensile properties of 9Cr-1MoVNb steel J Nucl Mater 132 1985 27 31
35. R.L. Klueh, and J.M. Vitek Tensile properties of 9Cr-1MoVNb and 12Cr-1MoVW steels irradiated to 23 dpa at 390 to 550 °C J Nucl Mater 182 1991 230 239
36. R.L. Klueh, and J.M. Vitek Fluence and helium effects on the tensile properties of ferritic steels at low temperatures J Nucl Mater 161 1989 13 23
37. 1/4Cr-1Mo steels R.E. Stoller A.S. Kumar D.S. Gelles Effects of radiation on materials: 15th international symposium, ASTM STP 1125 1992 American Society for Testing and Materials Philadelphia 1256 1266
38. W.L. Hu, and D.S. Gelles The ductile-to-brittle transition behavior of martensitic steels neutron irradiated to 26 dpa F.A. Garner C.H. Henager N. Igata Influence of radiation on material properties: 13th international symposium (Part II), ASTM STP 956 1987 American Society for Testing and Materials Philadelphia 83 97
39. Shamardin VK, Pecherin AM, Vishkarev OM, Borisov VP, Tulyakov GA. Investigation of the radiation-induced embrittlement of chromium steels. In: Proceedings of the international conference on radiation and material science. Alushta, USSR, 1990. p. 3-11
40. R.L. Klueh, and D.J. Alexander Impact behavior of 9Cr-1MoVNb and 12Cr-1MoVW steels J Nucl Mater 179-181 1991 733 736
41. C. Wassilew, and K. Ehrlich Effect of neutron irradiation on the dynamic fracture toughness behaviour of the 12% Cr steel MANET-1 investigated using subsize V-notch specimens J Nucl Mater 191-194 1992 850 854
42. R.L. Klueh, and D.J. Alexander Effect of irradiation in HFIR on tensile properties of Cr-Mo steels J Nucl Mater 187 1992 60 69
43. R.L. Klueh, D.J. Alexander, and M. Rieth The effect of tantalum on the mechanical properties of a 9Cr-2W-0.25V-0.07Ta-0.1C steel J Nucl Mater 273 1999 146 154
44. R.L. Klueh, D.S. Gelles, S. Jitsukawa, A. Kimura, G.R. Odette, and B. van der Schaaf Ferritic/martensitic steels-overview of recent results J Nucl Mater 307-311 2002 455 465
45. S. Jitsukawa, A. Kimura, A. Kohyama, R.L. Klueh, A.A. Tavassoli, and B. Van der Schaaf Recent results of the reduced activation ferritic/martensitic steel development J Nucl Mater 329-333 2004 243
46. S. Jitsukawa, M. Tamura, B. van der Schaaf, R.L. Klueh, A. Alamo, and C. Petersen Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H J Nucl Mater 307-311 2002 179 186
47. M.A. Sokolov, R.L. Klueh, G.R. Odette, K. Shiba, and H. Tanigawa Fracture toughness characterization of irradiated F82H in the transition region M.L. Grossbeck T.R. Allen R.G. Lott A.S. Kumar Effects of radiation on material: 21st international symposium, ASTM STP1447 2003 ASTM International West Conshohocken, PA
48. R.L. Klueh, M.A. Sokolov, K. Shiba, Y. Miwa, and J.P. Robertson Embrittlement of reduced-activation ferritic/martensitic steels irradiated in HFIR at 300 °C and 400 °C J Nucl Mater 283-287 2000 478 482
49. B. van der Schaaf, D.S. Gelles, S. Jitsukawa, A. Kimura, R.L. Klueh, and A. Moslang Progress and critical issues of reduced activation ferritic/martensitic steel development J Nucl Mater 283-287 2000 52 59
50. Fusion Technology: Annual report of the association CEA/EURATOM, 2000. p. 199-200
51. Nuclear Fusion Programme: Annual report of the association. Forschungszentrum Karlsruhe/EURATOM, October 1999-September 2000, Forschungszentrum Karlsruhe, FZKA 6550 and EUR 19707 EN, December 2000. p. 138-42
52. Fusion Technology: Annual report of the association CEA/EURATOM, 2000. p. 203-4
53. R. Lindau, A. Möslang, D. Preininger, M. Rieth, and H.D. Röhrig Influence of helium on impact properties of reduced-activation ferritic/martensitic Cr-steels J Nucl Mater 271&272 1999 450 454
54. E.V. van Osch, M.G. Horsten, G.E. Lucas, and G.R. Odette Mechanical properties of four 7-9%Cr reduced activation martensitic steels after 2.5 dpa, 300 °C irradiation M.L. Hamilton A.S. Kumar S.T. Rosinski M.L. Grossbeck Effects of irradiation on materials: 19th international symposium, ASTM STP 1366 2000 American Society for Testing and Materials West Conshohocken, PA 612 625
55. E.I. Materna-Morris, M. Rieth, and K. Ehrlich Irradiation behavior of ferritic/martensitic 9-12%Cr steels M.L. Hamilton A.S. Kumar S.T. Rosinski M.L. Grossbeck Effects of irradiation on materials: 19th international symposium, ASTM STP 1366 2000 American Society for Testing and Materials West Conshohocken, PA 597 611
56. K. Shiba, and A. Hishinuma Low-temperature irradiation effects on tensile and Charpy properties of low-activation ferritic steels J Nucl Mater 283-287 2000 474 477
57. E. Wakai, N. Hashimoto, Y. Miwa, J.P. Robertson, R.L. Klueh, and K. Shiba Effect of helium production on swelling of F82H irradiated in HFIR J Nucl Mater 283-287 2000 799 805
58. Y. Miwa, E. Wakai, K. Shiba, N. Hashimoto, J.P. Robertson, and A.F. Rowcliffe Swelling of F82H irradiated at 673 K up to 51 dpa in HFIR J Nucl Mater 283-287 2000 334 338
59. R.L. Klueh, and D.J. Alexander Embrittlement of 9Cr-1MoVNb and 12Cr-1MoVW steels irradiated in HFIR J Nucl Mater 187 1992 60 69
60. T. Morimura, A. Kimura, and H. Matsui Void swelling of Japanese candidate martensitic steels under FFTF/MOTA irradiation J Nucl Mater 239 1996 118 125
61. R. Kasada, A. Kimura, H. Matsui, and M. Narui Enhancement of irradiation hardening by nickel addition in the reduced-activation 9Cr-2W martensitic steel J Nucl Mater 258-263 1998 1199 1203
62. X. Jia, Y. Dia, and M. Victoria The impact of irradiation temperature on the microstructure of F82H martensitic/ferritic steel irradiated in a proton and neutron mixed spectrum J Nucl Mater 305 2002 1 7
63. Dia Y, Jai X. The behavior of martensitic steels after irradiation in SINQ target 3. In: Proceedings of conference on accelerator applications in a nuclear renaissance. La Grange Park, IL: American Nuclear Society; 2004:857-63
64. R.L. Klueh, D.J. Alexander, and E.A. Kenik Development of low-chromium, chromium-tungsten steels for fusion J Nucl Mater 227 1995 11 23
65. R.L. Klueh, D.J. Alexander, and P.J. Maziasz Bainitic chromium-tungsten steels with 3% chromium Met Trans A 28 1977 335 343
66. R.L. Klueh, and A.M. Nasreldin Microstructure and mechanical properties of a 3Cr-1.5Mo steel Met Trans A 18 1987 1279 1290
67. L.J. Habraken, and M. Economopoulos Bainitic microstructures in low-carbon alloy steels and their mechanical properties Transformation and hardenability in steels 1967 Climax Molybdenum Co. Ann Arbor, MI 69 107
68. R. Viswanathan, and W. Bakker Materials for ultrasupercritical coal power plants-boiler materials: part 1 J Mater Eng Perform 10 2000 81 95